• 제목/요약/키워드: high-level waste

검색결과 617건 처리시간 0.03초

고준위폐기물처분장 공학적방벽시스템의 열-수리-역학적 복합거동 해석 모델 개발 현황 (Current Status of the Numerical Models for the Analysis of Coupled Thermal-Hydrological-Mechanical Behavior of the Engineered Barrier System in a High-level Waste Repository)

  • 조원진;김진섭;이창수;최희주
    • 방사성폐기물학회지
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    • 제10권4호
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    • pp.281-294
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    • 2012
  • 현재까지 개발된 고준위폐기물 심지층처분장의 열-수리-역학적 복합거동 해석을 위한 전산 코드의 현황을 조사하고, 문헌에 보고된 각 코드에 의한 계산치와 현장실험 측정치의 비교 결과를 이용하여, 기존 전산 코드들의 신뢰도를 분석하였다. 개발된 전산코드들은 완충재가 없는 처분장에서는 붕괴열에 따른 암반의 열-수리-역학적 거동을 비교적 잘 모사하였으나, 포화 경암층에 위치한 완충재가 존재하는 처분장의 공학적방벽시스템 내에서 일어나는 열-수리-역학적 복합거동의 예측은 만족스럽지 못하였다. 현재 제안된 열-수리-역학적 복합거동 해석모델을 고준위폐기물 처분장 공학적방벽시스템의 거동 해석에 적용하기 위해서는 완충재 내의 수분함량 및 전 압력 분포를 보다 정교하게 모사할 수 있도록 수학적 모델의 개선이 필요하다.

DEVELOPMENT OF GEOLOGICAL DISPOSAL SYSTEMS FOR SPENT FUELS AND HIGH-LEVEL RADIOACTIVE WASTES IN KOREA

  • Choi, Heui-Joo;Lee, Jong Youl;Choi, Jongwon
    • Nuclear Engineering and Technology
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    • 제45권1호
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    • pp.29-40
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    • 2013
  • Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for spent fuel) for PWR and CANDU spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR spent fuels and 16,000 MtU of CANDU spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR spent fuel since 2007. However, since no decision was made for the CANDU spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.

고준위폐기물 처분연구용 지하터널의 기본설계 (Basic Design of the Underground Tunnel for the Research on High-level Waste Disposal)

  • 조원진;권상기;박정화;한필수
    • 방사성폐기물학회지
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    • 제2권4호
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    • pp.279-292
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    • 2004
  • 고준위폐기물 기준처분시스템의 건전성과 처분안전성의 실험적 검증에 필수적인 지하처분연구시설의 기본설계 도출을 위한 연구가 수행되었다. 먼저 지하처분연구시설의 부지에 대해 간단히 기술하고, 이 부지에 건설될 지하처분연구시설의 기본개념을 제시하고자 하였다. 제시된 기본개념을 충족시키기 위한 지하처분연구시설의 설계 요구사항을 설정하고, 이러한 기본개념과 설계요구사항을 바탕으로 지하처분연구시설의 기본설계를 수행하였다. 또 향후 지하처분연구시설에서 수행될 연구항목을 도출하였다.

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Extraction of Precipitated Calcium Carbonate from Oyster Shell waste and Its Applications

  • Ramakrishna, Chilakala;Thenepalli, Thriveni;Nam, Seong Young;Kim, Chunsik;Ahn, Ji Whan
    • 에너지공학
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    • 제27권1호
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    • pp.51-58
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    • 2018
  • In this paper, we reported that the influence of advanced functional mineral filler calcium carbonate ($CaCO_3$) extracted from oyster shell waste, which are rich mineral sources of $CaCO_3$. Oyster Shells, available in abundance, have no eminent use and are commonly regarded as waste. Their improper disposal causes a significant level of environmental concern and also results in a waste of natural resources. Recycling shell waste could potentially eliminate the disposal problem, and also turn an otherwise useless waste into high value added products. Oyster shell waste calcination process to produce pure lime (CaO) which have good anti-microbial property for waste water treatment and then focuses on its current applications to treat the coffee waste and its effluents for biological treatment and utilization as a fertilizers.

Reprocessing of spent nuclear fuel in carbonate media: Problems, achievements, and prospects

  • Stepanov, Sergei I.;Boyarintsev, Alexander V.
    • Nuclear Engineering and Technology
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    • 제54권7호
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    • pp.2339-2358
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    • 2022
  • The review discusses various alternative approaches for spent nuclear fuel (SNF) reprocessing in aqueous carbonate media. The main stages, schemes, and methods of the most well-known and well-described processes for reprocessing SNF and some high-level radioactive waste using carbonate systems developed by research groups in Japan, the United States of America, the Republic of Korea, and the Russian Federation described and compared. The main advantages of such methods are outlined compared to the SNF reprocessing in nitric acid media. The levels of development and proximity of the designed processes to the industrial implementation are shown. The main principle achievements, prospects, and routes for the refinement of such methods for the technology of SNF reprocessing and handling of high-level radioactive waste formulated.

Effect of crushed waste glass as partial replacement of natural fine aggregate on performance of high strength cement concrete

  • Ajmal, Paktiawal;Mehtab, Alam
    • Advances in materials Research
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    • 제11권4호
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    • pp.251-277
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    • 2022
  • Disposal of industrial waste in cities where municipal authorities permitting higher floor area ratio coupled with increasing living standards, a lot of demolition waste is being generated. Its disposal is a challenge particularly in megacities where no landfills are available. The ever-increasing cost of building construction materials also necessitates consuming demolition wastes in a useful manner to save fresh natural raw materials. In the present work, the crushed waste glass is used in high-strength concrete as a partial replacement of fine aggregate. The control concrete of grade M60 was proportioned following BIS 10262-2009. The crushed waste glass has been used as a partial replacement with varying percentages of 10, 20, 30, and 40% by weight of fine aggregate. Experimental tests were carried on the fresh and hardened state of the concrete. The effect of crushed waste glass on the workability of the concrete has been investigated. Non-destructive tests, acid attack tests, compressive strength, split tensile strength, and X-ray diffraction analysis was carried out for the control concrete and concrete containing crushed waste glass after 7, 28, and 270 days of normal curing. The results show that for the same w/c ratio, the workability of concrete increases with increasing replaced crushed waste glass content. However, the decrease in compressive strength of the concrete after 28 days of normal curing and further after 28 days of acid attacks, up to 30% replacement level of fine aggregate by the crushed waste glass is insignificant.

Conceptual design of ultra-high performance fiber reinforced concrete nuclear waste container

  • Othman, H.;Sabrah, T.;Marzouk, H.
    • Nuclear Engineering and Technology
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    • 제51권2호
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    • pp.588-599
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    • 2019
  • This research presents a structural design of high-level waste (HLW) container using ultra-high performance fiber reinforced concrete (UHP-FRC) material. The proposed design aims to overcome the drawbacks of the existing concrete containers which are heavy, difficult to fabricate, and expensive. In this study, the dry storage container (DSC) that commonly used at Canadian Nuclear facilities is selected to present the proposed design. The design has been performed such that the new UHP-FRC alternative has a structural stiffness equivalent to the existing steel-concrete-steel container under various loading scenarios. Size optimization technique is used with the aim of maximizing stiffness, and minimizing the cost while satisfying both the design stresses and construction requirements. Then, the integrity of the new design has been evaluated against accidental drop-impact events based on realistic drop scenarios. The optimization results showed: the stiffness of the UHP-FRC container (300 mm wall thick) is being in the range of 1.35-1.75 times the stiffness of existing DSC (550 mm wall thick). The use of UHP-FRC leads to decrease the container weight by more than 60%. The UHP-FRC container showed a significant enhancement in performance in comparison to the existing DSC design under considered accidental drop impact scenarios.

고준위방사성폐기물 처분 관련 자료 관리 해외사례 분석 (Analysis of Overseas Data Management Systems for High Level Radioactive Waste Disposal)

  • 김민정;박선주;김혜림;윤운상;박정훈;이정환
    • 지질공학
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    • 제33권2호
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    • pp.323-334
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    • 2023
  • 고준위방사성폐기물 처분을 위한 다양한 조사와 연구를 진행하는 과정에서 막대한 양의 자료가 생산되며 이를 관리하기 위한 자료 관리가 필요하다. 스웨덴의 SKB는 SICADA를 구축하여 부지선정, 평가, 해석, 분석 및 모델링에 활용할 수 있게 하였고, 독일의 BGE는 부지선정법에 따라 자료를 관리하기 위해 데이터베이스 및 문서 관리시스템 ArbeitsDB와 자료시스템 ELO를 구축하였다. 영국의 NWS는 DMS를 구축하여 연구, 조사 자료를 관리할 수 있도록 하였다. 미국의 DOE와 OCRWM은 부지특성화 조사를 진행하면서 자료 관리 및 이후의 인허가 절차를 위하여 TDMS를 구축하였다. 해외사례 조사, 분석을 통해 자료의 품질관리와 자료 활용의 확장성이 자료 관리에 있어 중요한 부분임을 확인할 수 있다. 향후 우리나라도 장기적인 관점에서 자료의 품질관리와 확장성을 고려한 자료 관리 개념을 확립하고 그에 맞춘 자료 관리 시스템 및 체계를 구축해야 할 것이다.

양돈폐수 처리에 의한 포플러클론의 산화스트레스와 항산화반응 (Oxidative Stress and Antioxidant Responses in Poplar Clones Irrigated with Livestock Waste Leachate)

  • 제선미;여진기;우수영
    • 한국농림기상학회지
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    • 제13권3호
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    • pp.140-147
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    • 2011
  • 고온과 고광으로 인해 항산화요구도가 높은 8월 시기에 포플러클론들의 산화피해와 항산화반응에 대하여 양돈폐수의 영향에 대하여 알아보았다. 잎의 이온유출량과 항산화효소 APX와 GR의 활성, 그리고 카로테노이드 함량을 조사였다. 포플러클론의 양돈폐수 처리에 따른 산화피해와 항산화반응은 다양하게 나타났다. 산화스트레스로 인한 세포막 피해 수준을 알 수 있는 이온유출량 기준으로, 크게 세 그룹으로 분류하였다. 첫번째 그룹은 세포막 피해수준이 대조구보다 높게 나타난 클론들로서 Eco 28, 62-10, Bonghwa1, Dorskamp가 포함되었다. 이들 그룹은 양돈폐수 처리로 인한 고농도 질소함량이 스트레스로 작용하여 여름철 항산화요구도가 더욱 가중된 것으로 보인다. 그래서 결과적으로 활성산소에 대한 항상성을 유지하지 못하였다. 두번째 그룹은 세포막 피해수준이 대조구와 유사한 Suwon, 72-30, 72-31 이었다. 세 번째 그룹은 세포막 피해수준이 대조구보다 낮게 나타난 97-18 이었다. 97-18 클론의 경우 양돈폐수 처리로 인해 공급된 질소가 여름철 산화스트레스에 대한 피해를 경감시켜, 양돈폐수 처리로 인한 여름철 산화피해가 가장 적은 클론으로 나타났다. 이러한 결과들은 양돈폐수로 인한 고농도 질소가 클론마다 서로 다르게 작용할 수 있음을 의미한다. 생장시기인 여름철에 가중되는 산화피해는 전체 생중량에 영향을 주어 양돈폐수 정화능력에도 영향을 미칠 수 있을 것으로 생각된다. 그러나 이러한 부분에 대해 추후 연구가 더 필요하다.

ICT기반 폐플라스틱 관리 전주기 기술 동향 (ICT-based Waste Plastic Management Life Cycle Technology)

  • 문영백;정훈;허태욱
    • 전자통신동향분석
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    • 제37권4호
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    • pp.28-35
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    • 2022
  • To solve the challenge of waste plastics, this study investigated the related technologies and company trends along the plastic life cycle, and primarily describes ICT technologies to improve efficiency in the process of sorting and sorting waste plastics. Waste plastic discharge caused by the explosive increase in parcel traffic because of COVID-19 is also growing exponentially. Hence, waste treatment is emerging as a social challenge. Most of the domestic waste classification depends on the manual process according to the waste pollution level. The plastic material classification approach using the spectroscopy approach reveals a high error in the contaminated waste plastic classification, but if the Artificial Intelligence-based image classification technology is employed together, the classification precision can be enhanced because of the type of waste plastic product and the contaminated part can be differentiated.